34results about How to "Reduce Radiation Risk" patented technology

The invention discloses a metal thermoelectric potential detection instrument comprising a measuring device and a control device which controls the measuring device. The measuring device comprises a box body with a work board, a fixing device which fixes metal to be detected on the work board, a first probe component which can be movably arranged in the box body along an X-axis direction and a Z-axis direction, a second probe component which can be movably arranged in the box body along the Z-axis direction, an X driving mechanism which is used for driving the first probe component to move in the X-axis direction, and a first Z driving mechanism and a second Z driving mechanism which are respectively used for driving the first probe component and the second probe component to move in the Z-axis direction. The X-axis and the Z-axis are mutually perpendicular, and the Z-axis is perpendicular to the work board. The metal thermoelectric potential detection instrument is convenient to carry and can measure various sizes of metal parts in the industrial field so that the metal thermoelectric potential detection instrument is high in reliability and has certain automation function.

The invention relates to the technical field of CT (computed tomography) system parameter calibration, in particular to a C-arm system rotational angle calibration device and a C-arm system calibration method; the C-arm system rotational angle calibration device comprises a motion conversion component, a displacement sensor, a data transmitter and a processor, the motion conversion component is arranged to connect with a C-arm and convert rotational motion of the C-arm into linear motion, the displacement sensor is connected with the motion conversion component and is arranged to acquire a displacement signal of the motion conversion component and transmit the displacement signal to the data transmitter connected with the displacement sensor, and the processor is connected with the data transmitter and is arranged to receive and analyze the displacement signal transmitted by the data transmitter. The C-arm system rotational angle calibration device is simple to operate, good in operational stability and reliability, and free of X-ray exposure in use, so that the radiation risk can be lowered.

The invention discloses a microwave heating treatment system for high-radioactivity nuclear industry waste, and relates to the technical field of treatment of the high-radioactivity nuclear industry waste. The microwave heating treatment system comprises a sealing box and a control system. A microwave heating hole is formed in the top of the sealing box. A lifting device is arranged below the microwave heating hole. A sealing door is arranged on the sealing box. A first conveyor for feeding or taking a barrel containing high-radioactivity waste liquid to or away from the lifting device is arranged in the sealing box. A second conveyor is arranged on the outer portion of the sealing box. The control system comprises a touch screen and a PLC (programmable logic controller) electrically connected with the touch screen. The PLC is connected with the first conveyor, the second conveyor, the microwave heating hole and the lifting device electrically. The microwave heating treatment system has the advantages that automatic delivering, sealing, and microwave heating and evaporating of the barreled high-radioactivity waste liquid are realized, the whole process does not need manual on-siteoperations, and no high-radioactivity waste liquid exists on an equipment maintenance site, so that working efficiency is improved, and the risk that operators are radiated is reduced.

The invention discloses a low-dose CT tooth image denoising method based on a double-residual network, and the method comprises the steps: firstly training an auxiliary network, and storing a model; and calculating a loss function value by utilizing a similarity relationship between the feature space diagrams extracted by the double-residual network, and updating parameters by combining the loss function value between the denoising network and the double-residual network so as to assist the training of the denoising network. The method mainly comprises a data loading module, an auxiliary network training module, a double-residual network denoising module and a testing module. The low-dose CT tooth image denoising method has a remarkable effect on low-dose CT tooth image denoising, can reserve some detail features of the image, and has important application value.

The invention discloses a control method, a control system and a control device of auto-exposure of C-arm X-ray machines. The device collects images according to the setting exposure parameter, analyzes images, adjusts the exposure parameter and collects images again. Through such a rapid and continuous process of collection and adjustment, the control device of auto-exposure of C-arm X-ray machine realizes auto-exposure control, eases the burden of doctors and reduces the surgical risk by automatically outputting and locking the optimal exposure parameter in a short time. the control device of auto-exposure of C-arm X-ray machine also realizes consistency of the diagnostic images of different body parts of patients in different body sizes; in addition to meeting the diagnosis quality demand of images, the device also minimizes the radiation level of rays and reduces the radiation risk of doctors and patients.

The invention belongs to the technical field of high-radioactive nuclear industry waste microwave heating treatment and particularly relates to high-radioactive nuclear industry waste microwave heating treatment equipment with an aim to solve problems that in a microwave heating device, high-radioactive liquid waste usually contains more solid waste resulting in proneness to pipe clogging, influence of process efficiency and increasing of radiation risks in the prior art. The technical scheme includes that the high-radioactive nuclear industry waste microwave heating treatment equipment comprises a sealed box, a microwave heating hole is arranged in the top of the sealed box, a lifting device is arranged under the microwave heating hole, a sealing door is arranged on the sealed box, a first conveying device used for conveying a barrel containing high-radioactive liquid waste to the lifting device or away form the same is arranged n the sealed box, a second conveying device is arrangedon the outside of the sealed box, and the first conveying device and the second conveying device are matched in height and are respectively located on two sides of the sealing door. The high-radioactive nuclear industry waste microwave heating treatment equipment is applied to microwave evaporation of the high-radioactive liquid waste.

The invention discloses a route planning method under the nuclear radiation environment. The route planning method comprises the following steps: S1, in order to prevent workers from colliding obstacles in a walking process, swelling the obstacles; S2, in a map which the obstacles have been swelled on, generating a point set V containing the appointed number of random points; on a free space whichthe random points exist in, avoiding collision with the obstacles; S3, performing partial planning, connecting elements in the random point set V two by two, constructing a set E related to side lengths after collision detection and calculating out dosage values corresponding to all the side lengths through a dosage function at the same time; S4, inputting a starting point qI and a terminal pointqG and connecting the starting point and the terminal point into the side length set E according to the S2; S5, utilizing an A*algorithm to perform discrete searching to obtain a side sequence and forming a route from the qI to the qG through the obtained side sequence. The route planning method disclosed by the invention utilizes a random route diagram method to find routes under the nuclear radiation environment, has a small calculation amount, can quickly find the route with the complete probability and reduces radiation risk.

The invention discloses a spent fuel storage pool system which comprises a spent fuel storage pool and a purification unit, the purification unit is arranged in the spent fuel storage pool and comprises a pump and a purification section, the pump is communicated with the input end of the purification section, the pump is used for conveying pool water in the spent fuel storage pool to the purification section, and the purification section is communicated with the pump. The purification section is used for purifying the pool water conveyed by the pump, and the output end of the purification section is communicated with the spent fuel storage water pool so as to discharge the purified pool water and return the purified pool water to the spent fuel storage water pool. The invention further discloses an installation / replacement method of the filter element of the spent fuel storage pool system. The system provided by the invention can realize in-pool purification, and compared with the prior art, the system provided by the invention can solve the problems of insufficient treatment capacity and the like of out-pool purification, and can meet the operation requirements of large spent fuel storage pools. The method can realize remote maintenance and replacement.

The invention discloses a method for reducing the radiation of an X-ray detection environment. The method comprises the following steps: S1, setting an X-ray shielding structure at an X-ray generationdevice, wherein the X-ray shielding structure shields an X-ray bulb tube, and X-rays emitted by the X-ray bulb tube are ejected from an ejection port of the X-ray generation device; S2, a receiving end: setting a protective medium and a first shielding plate on a detected person, wherein a detected person is located between the protective medium and the first shielding plate and the protective medium covers a detected part of the detected person, and setting an X-ray digital detector used for imaging between the detected person and the first shielding plate, wherein the protective medium is arranged between the X-ray generating device and the detected part; and S3, an operation end: setting a second shielding plate between the operator and the X-ray generation device. According to the invention, the X-ray radiation in the environment is greatly reduced, so that the problem of X-ray radiation in special scenes such as a non-protection room and the like is solved.

The invention discloses a radiation dose rate measurement system based on a high-purity germanium detector. The radiation dose rate measurement system comprises a measurement unit, a simulation unit, a comparative analysis unit and a data processing unit, the measurement unit is used for performing an energy spectrum measurement experiment on the energy spectrum of the radiation source to obtain a real energy spectrum of the radiation source; the simulation unit is used for carrying out Monte Carlo simulation on the energy spectrum measurement experiment to obtain a simulation energy spectrum of the radiation source, and the simulation unit also simulates the radiation source under different energies based on the Monte Carlo simulation experiment after parameter optimization to obtain a continuous energy spectrum of the radiation source; the comparative analysis unit is used for comparing and analyzing the real energy spectrum and the simulated energy spectrum, and performing parameter optimization on the Monte Carlo simulation experiment; and the data processing unit is used for performing energy spectrum dose conversion according to the continuous energy spectrum and obtaining the radiation dose rate based on the energy spectrum dose conversion. The energy spectrum-dose conversion function can be accurately obtained by measuring the energy spectrum of the radiation source and combining the Monte Carlo simulation technology, and then the radiation dose rate is obtained.

The invention relates to coolant rotational-flow purification methods and devices for boron removal sections of boron recycle systems and provides a coolant rotational-flow purification method for a boron removal section of a boron recycle system. The method comprises the following steps that (i) a micro-rotational-flow separation complete device is provided, wherein the device comprises a shell (1), a micro-cyclone core tube (3) and a dust hopper (9); the shell (1) comprises an upper cavity, a middle cavity (6) and a lower cavity; the micro-cyclone core tube (3) is arranged in the middle cavity (6); the dust hopper (9) is arranged in the upper cavity; (ii) in the boron removal section, reactor coolant distillate is fed into the middle cavity of the micro-rotational-flow separation complete device after boron removal is performed, and rotational-flow separation is performed on the distillate through the micro-cyclone core tube to separate solid impurity particles from the distillate to obtain concentrate containing the solid impurity particles and clear liquid; (iii) the obtained concentrate is fed into the upper cavity to be settled in the dust hopper, so that filtrate is obtained; (iv) the obtained filtrate and the obtained clear liquid converge and then flow to downstream equipment.

The invention discloses a functional modular plutonium contaminated soil ex-situ leaching decontamination method. According to the invention, a contaminated soil particle size grading and analysis module, a contaminated soil screening and volume reduction pretreatment module, a contaminated soil grading leaching decontamination module and a waste liquid treatment and recycling module are included. According to the method, on the basis of particle size grading and analysis of the contaminated soil, mass volume reduction of the contaminated soil and reduction of comprehensive decontamination cost are preliminarily achieved through screening pretreatment, grading leaching decontamination is conducted on the remaining part, the content of plutonium-239 in the contaminated soil is reduced to 3700 Bq / kg or below 100 Bq / kg, then waste liquid generated in the leaching process is treated, and exempt emission or reuse of the waste liquid is achieved. Compared with the prior art, the process is constructed in a function modularization mode, optimization of subsequent core technical parameters and construction of matched technical equipment are guided, all modules can be disassembled, matched and integrated according to specific requirements, and then the flexibility of process operation is improved.

The invention provides a structure for reducing dangerous medium leakage of a filter, the structure comprises a filter body and a filter cover plate, an inner sealing ring is arranged between the filter body and the filter cover plate, and the outer side of the inner sealing ring is provided with a leakage guide channel leading to the outside for collecting leaked dangerous media. The structure for reducing the dangerous medium leakage of the filter has a good sealing effect, can directly collect the leaked dangerous medium, and greatly reduces the risk that the dangerous medium leaks to a plant, so that the shutdown frequency of a power plant unit is further reduced, and radiation protection optimization is realized. In addition, the invention further provides a method for reducing leakage of the dangerous medium of the filter, the method prevents the dangerous medium from directly leaking to a plant, and the radiation risk of the plant is reduced.

The invention discloses a waste barrel transferring and welding sealing system which comprises a transferring device, a welding device, a rotating device and a detecting device, the transferring device is used for transferring waste barrels, and the transferring device comprises a barrel inlet roller way and a barrel outlet roller way; the welding device is used for welding and sealing the waste barrels conveyed on the barrel feeding roller way; the detection device is used for carrying out surface pollution detection on the surface of the waste bin; the rotating device is arranged between the barrel inlet roller way and the barrel outlet roller way, the two ends of the rotating device are connected with the outlet end of the barrel inlet roller way and the inlet end of the barrel outlet roller way correspondingly, and the rotating device is used for receiving the waste barrels on the barrel inlet roller way, driving the waste barrels to rotate when the detection device conducts surface pollution detection on the waste barrels and driving the waste barrels to rotate when the detection device conducts surface pollution detection on the waste barrels. And the detected waste barrels are conveyed to a barrel discharging roller way. The working efficiency of waste barrel transferring and welding sealing can be improved, and the radiation risk of operators is reduced.

The invention discloses a method and system for selecting a single event locking effect protection resistor, and the method comprises the steps: giving a locking current value according to an obtainedsingle event locking effect electrical parameter test result of a to-be-protected object; analyzing normal working electrical performance conditions of the to-be-protected object, and determining a normal working voltage value and a normal working current value of the to-be-protected object under the working condition, and a power supply voltage value data range during normal working; determininga minimum value of a series resistor of the to-be-protected object according to the locking current value and the normal working voltage value; determining a maximum value of the series resistor of the to-be-protected object according to the normal working current value and the minimum power supply voltage value; and determining a selection result of the series resistor of the to-be-protected object according to the determined minimum value and maximum value of the series resistor of the to-be-protected object. According to the invention, the protection problem of single event locked sensitive devices such as COTS devices and the like in space application can be solved.

The invention discloses a metal thermoelectric potential detection instrument comprising a measuring device and a control device which controls the measuring device. The measuring device comprises a box body with a work board, a fixing device which fixes metal to be detected on the work board, a first probe component which can be movably arranged in the box body along an X-axis direction and a Z-axis direction, a second probe component which can be movably arranged in the box body along the Z-axis direction, an X driving mechanism which is used for driving the first probe component to move in the X-axis direction, and a first Z driving mechanism and a second Z driving mechanism which are respectively used for driving the first probe component and the second probe component to move in the Z-axis direction. The X-axis and the Z-axis are mutually perpendicular, and the Z-axis is perpendicular to the work board. The metal thermoelectric potential detection instrument is convenient to carry and can measure various sizes of metal parts in the industrial field so that the metal thermoelectric potential detection instrument is high in reliability and has certain automation function.

The invention discloses a radiotherapy X-ray source and an X-ray source device, and relates to the technical field of radiotherapy. The radiotherapy X-ray source comprises a substrate; a cold cathodeelectron emission source disposed on the substrate; an anode transmission target disposed opposite to the cold cathode electron emission source, wherein an electric field can be applied between the anode transmission target and the substrate; and a filter disposed on a side of the anode transmission target away from the cold cathode electron emission source. The substrate, the cold cathode electron emission source, the anode transmission target, and the filter are encapsulated in a vacuum chamber. The X-ray source device uses the radiotherapy X-ray source, and further includes a focusing lensand a beam limiter. Compared with the prior art, the radiotherapy X-ray source provided by the invention has electron escape through the cold cathode field emission, does not need to preheat a cathodematerial, and has low power consumption. The cathode material uses an array arrangement and has high electron emission efficiency. The X-ray source device uses the transmission target and has a smallsize and high X-ray generation efficiency.

The invention discloses a functional modular plutonium-contaminated soil ectopic leaching and decontamination method, comprising a soil particle size classification and analysis module, a pre-treatment module for soil screening and capacity reduction, a soil grading, leaching and decontamination module, a waste Four modules including liquid treatment and reuse module. This method is based on the particle size classification and analysis of polluted soil, and first preliminarily realizes volume reduction of contaminated soil through pre-screening treatment to reduce the cost of comprehensive decontamination, and then decontaminates the remaining part by graded leaching to remove the plutonium in the contaminated soil. 239 content is reduced to 3700Bq / kg or below 100Bq / kg, and then the waste liquid generated in the washing process is treated to realize its exemption from discharge or reuse. Compared with the existing technology, constructing the process in a functional modular way is not only conducive to guiding the optimization of subsequent core technical parameters and the construction of supporting technical equipment, but also dismantling, collocation and integration of each module according to specific needs, and then Increased flexibility in process operations.

The system comprises a supply system, a sampling system, a receiving system, a transmission pipeline system and a control system, the control system is electrically connected with the supply system, the transmission pipeline system, the sampling system and the receiving system, and the supply system is used for sending empty sample bottles according to the control of the control system; the conveying pipeline system is respectively connected with the supply system and the sampling system and is used for conveying the empty sample bottles to the sampling system according to the control of the control system, the sampling system is used for receiving the empty sample bottles and sampling according to the control of the control system to obtain the sample bottles and sending the sample bottles, and the conveying pipeline system is also connected with the receiving system. The conveying system is further used for conveying the sample bottles to the receiving system according to control of the control system; the receiving system is used for receiving the sample bottles according to control of the control system. The full-automatic sample taking and sending device can realize full-automatic sample taking and sending, reduces the misoperation risk of personnel, saves the sample taking and sending time, and can be suitable for sample taking and sending application of large factories.

The invention relates to a position assist device for medical imaging common X-ray radiography. The assist device comprises a pressing filling device body, an assist fixing body, a booster device body, a Water's position assist body, an anti-Stenver's position assist body and a base, wherein the pressing filling device comprises a first wedge-shaped body, a second wedge-shaped body and a third wedge-shaped body; the assist fixing body comprises a bottom plate, a 45-degree inclined plate, a humerus booster body, a thumb side position assist body, a thumb ortho position assist body, a first four-finger assist body and a second four-finger assist body; the booster device comprises a first booster plate, a second booster plate, a third booster plate, a fourth auxiliary pressing plate and a fourth main pressing plate; a concave area, a ball area, a fan-shaped area, an angle reference plate area and a foot side position pressing area are arranged on the base. The position assist device has the advantages as follows: the total detection time and the number of detection times of a sick child are reduced, the work efficiency of medical workers is improved, various artifacts in an image are effectively reduced or eliminated, and the quality of the image is improved.

A method for judging the enhancement effect of low-dose-rate radiation damage, comprising the steps of: 1) obtaining the test results of electrical parameters of the object to be tested before irradiation; 1. Ionizing radiation tests with different biases to obtain electrical parameter test results at multiple irradiation dose points; 3) determining the ratio of the electrical parameter degradation of the object to be tested and the reliability influencing factor of the electrical parameter degradation of the object to be tested ; 4) According to the ratio of the electrical parameter degradation amount and the electrical parameter degradation reliability impact factor, it is determined whether the object to be tested has a low dose rate radiation damage enhancement effect. The present invention obtains comparative data of high and low dose rates by carrying out high and low dose rate irradiation tests respectively, and obtains whether aerospace components have low dose rate radiation damage by considering the component parameter degradation factor and the size of low dose rate radiation damage enhancement factor Judgment results of reinforcement effects.

The invention relates to the technical field of high intensity proton cyclotron beam commissioning devices, in particular to a beam commissioning target apparatus for a high intensity proton cyclotron. The high intensity proton cyclotron beam commissioning apparatus comprises a fixed stander, wherein the fixed stander is fixedly provided with a first fixed plate, a vacuum protection cover is arranged above the first fixed plate, the vacuum protection cover is provided with a beam passage, a commissioning target head is arranged in the vacuum protection cover, an air cylinder is fixedly arranged below the first fixed plate, an intermediate assembly is arranged between the air cylinder and the target head, when the air cylinder makes the extension movement, the intermediate assembly is driven to drive the target head to move upwardly, a terminal position of the target head is just located in the beam passage, when the air cylinder makes the retraction movement, the intermediate assemblyis driven to drive the target head to move downwardly to be away from the target head, and the beam passage is communicated, so that the beam commissioning target and an experimental terminal beam line share the same beam line, and the manpower cost and the resource cost can be greatly reduced.

The invention discloses a space active excited X-ray fluorescence detector. The detector comprises a probe arranged on an inspector X panel and a moonlit survival guarantee apparatus, the probe is electrically connected to an inspector cabin comprehensive electronics plate; the moonlit survival guarantee apparatus comprises an active radiation heat source, an external support and a thermal control coating, the active radiation heat source is positioned in the thermal control coating, the thermal control coating is fixed on the inspector X panel through the external support; wherein, when the space active excited X-ray fluorescence detector is in a moonlit night state, the active radiant heat source is relative to the rear end of a probe, and provides active temperature control to the probe. The space active excited X-ray fluorescence detector has autonomous insulation capability, moon survival capability of the equipment can be greatly increased, and detection capability can be simultaneously increased.

The invention provides a device for receiving and sampling radioactive drugs. The device comprises a synthesizer (1), a pipeline A (2), a sterile filtration membrane A (3), a three-way valve A (4), a sampling syringe (5), a product receiving bottle (6), a pipeline B (7), a sterile filtration membrane B (8) and a three-way valve B (9), and is characterized in that the pipeline A (2) is connected to the synthesizer (1), the three-way valve A (4) is arranged on the pipeline A (2) and is connected with the sampling syringe (5), the other end of the pipeline A (2) is arranged in the product receiving bottle (6), the pipeline B (7) is also arranged in the product receiving bottle (6), the sterile filtration membrane B (8) and the three-way valve B (9) are connected to the pipeline B (7), and the three-way valve B (9) is positioned at the right end of the sterile filtration membrane B (8). By using the device disclosed by the invention, the operations of operators during production can be reduced, the radiation risk is reduced, and the contamination risks in product receiving and sampling processes are reduced.

The invention discloses a method for setting a nuclear level indicator for a pressure vessel, which comprises the following steps of: 1) determining the mounting position of the nuclear level indicator on the pressure vessel according to an operation level in the pressure vessel; 2) according to the mounting position of the nuclear level indicator, determining the installation sequence of the nuclear level indicator as follows: a, the built-in nuclear source sleeve is installed; b, setting a nuclear emission source; c, surfacing the annular boss; d, a non-penetrating hole is machined; and e, installing a nuclear ray receiver. According to the method for setting the nuclear level gauge, the depth of the non-penetrating open pore can be greatly improved, so that the penetrability of rays of the nuclear level gauge is improved, the dosage of a nuclear source is reduced, and the economic cost and additional radiation risk of the nuclear level gauge are reduced.

The invention discloses a kit for thoracolumbar vertebral pedicle operation, and a use method thereof. The kit comprises a development grid, Kirschner wire sets and a scenograph, wherein the development grid is clung to the skin in the focus area; each Kirschner wire set is inserted into each vertebral pedicle area. The use method comprises the following steps: firstly, after perspective positioning of the development grid, the position of the injured vertebral pedicle is checked, and a puncture mark is made on the skin of the focus spine of a patient for accurate positioning; three Kirschner wires are adopted for percutaneous penetration in a triangular manner in each vertebral pedicle area, according to the vertebral pedicle areas (2 degrees on right and 10 degrees on left) after perspective treatment, the Kirschner wires at the optimal positions are indwelled, and screw paths are expanded to enter the vertebral body through the vertebral pedicle. According to the kit for thoracolumbar vertebral pedicle operation and the use method thereof, the development grid and the Kirschner wire sets are combined to realize successful one-time puncture positioning, so that repeated puncture is avoided, and the operation time is shortened; tissue damages and bleeding are reduced; the X-ray radiation risk of patients and physicians is reduced.